JP2529994B2 - In-reactor inspection device - Google Patents
In-reactor inspection deviceInfo
- Publication number
- JP2529994B2 JP2529994B2 JP63079711A JP7971188A JP2529994B2 JP 2529994 B2 JP2529994 B2 JP 2529994B2 JP 63079711 A JP63079711 A JP 63079711A JP 7971188 A JP7971188 A JP 7971188A JP 2529994 B2 JP2529994 B2 JP 2529994B2
- Authority
- JP
- Japan
- Prior art keywords
- arm
- main body
- reactor
- core
- support
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Fee Related
Links
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】 〔発明の目的〕 (産業上の利用分野) 本発明は沸騰水型原子炉(以下BWRという)の内部に
収容される炉心支持板等炉内構造物の探傷等の検査を行
なうのに好適な原子炉内検査装置に係り、特に、炉心支
持板等の炉内構造物の検査を自動的に行なうことができ
るようにした原子炉内検査装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial field of application) The present invention relates to the inspection of internal structures such as a core support plate and the like inside a boiling water reactor (hereinafter referred to as BWR) for flaw detection. The present invention relates to an in-reactor inspection apparatus suitable for inspecting, and more particularly, to an in-reactor inspecting apparatus capable of automatically inspecting an in-reactor structure such as a core support plate.
(従来の技術) 一般に、BWRは第8図に示すように構成され、原子炉
圧力容器1内には炉心2が冷却材3により冠水された状
態で収容され、炉心2は炉心支持構造物4により支持さ
れている。(Prior Art) Generally, a BWR is configured as shown in FIG. 8, and a reactor pressure vessel 1 accommodates a core 2 submerged by a coolant 3, and the core 2 has a core support structure 4 It is supported by.
炉心2は図示しない複数の燃料集合体および制御棒等
から構成されており、制御棒は制御棒駆動機構5によっ
て炉心2内へ挿入度が調節され、それによって炉心出力
が制御される。The core 2 is composed of a plurality of fuel assemblies (not shown), control rods and the like. The control rod drive mechanism 5 adjusts the degree of insertion of the control rods into the core 2, thereby controlling the core output.
冷却材3は炉心2を図中上方に向って昇流し、その昇
流の際に炉心2の核反応熱を冷却する一方で加熱されて
昇温する。昇温した冷却材3は水と蒸気との二相流とな
って、炉心2の上方に設置された気水分離器6内に導入
される。The coolant 3 flows upward in the core 2 in the figure, and while the coolant 3 cools the nuclear reaction heat of the core 2 while being heated, it is heated and its temperature rises. The heated coolant 3 becomes a two-phase flow of water and steam, and is introduced into a steam separator 6 installed above the core 2.
この気水分離器6内にて液相と分離された蒸気はその
上方に設置された蒸気乾燥器7内に導入されて乾燥蒸気
となる。The steam separated from the liquid phase in the steam separator 6 is introduced into the steam dryer 7 installed above the steam to become dry steam.
この乾燥蒸気は原子炉圧力容器1に接続された主蒸気
配管8を介して図示しないタービン系の蒸気タービンに
移送されて発電に供される。This dry steam is transferred to a steam turbine (not shown) of a turbine system via a main steam pipe 8 connected to the reactor pressure vessel 1 and used for power generation.
蒸気タービンで仕事をした蒸気は図示しない復水器内
に導入されて凝縮・液化されて復水となる。この復水は
復水浄化系(図示せず)を介して再度原子炉圧力容器1
内に戻される。The steam that has worked in the steam turbine is introduced into a condenser (not shown), condensed and liquefied to be condensed water. This condensate is again supplied to the reactor pressure vessel 1 via a condensate purification system (not shown).
Returned inside.
一方、気水分離器6で分離された水は原子炉圧力容器
1内のダウンカマ部を流下して上記給水と混合した状態
で再度炉心2の下方に供給される。以下これらの作用が
繰返される。On the other hand, the water separated by the steam separator 6 flows down through the downcomer section in the reactor pressure vessel 1 and is mixed with the above-mentioned feed water to be supplied below the core 2 again. These actions are repeated thereafter.
ところで、上記炉心支持構造物4は第9図に示すよう
に構成され、上部格子板9の複数の格子目内に複数の燃
料集合体を垂直方向にそれぞれ挿通して、各燃料集合体
の上部の位置決めを行なう。By the way, the core support structure 4 is configured as shown in FIG. 9, and a plurality of fuel assemblies are vertically inserted into a plurality of grids of the upper grid plate 9 to form an upper portion of each fuel assembly. Position.
上部格子板9の下方に配置された炉心支持板10は複数
の燃料集合体の下部を支持して位置決めを行なってい
る。これら上部格子板9および炉心支持板10は円筒状の
炉心シュラウド11内に収容されている。A core support plate 10 arranged below the upper lattice plate 9 supports the lower parts of a plurality of fuel assemblies for positioning. The upper lattice plate 9 and the core support plate 10 are housed in a cylindrical core shroud 11.
炉心支持板10は第10図に示すように構成され、円筒状
の胴12内にはその直径方向に複数の補強板13,13…がほ
ぼ平行に並設されて胴12が補強され、各補強板13,13…
同士は接続棒14,14により接続されて固定され、胴12の
開口上端には円形の上板15が周溶接16により溶着され、
上板15には図示しない燃料集合体の支持金具の下部を嵌
入させて支持する支持用嵌合穴15aを複数配設してい
る。The core support plate 10 is configured as shown in FIG. 10, and a plurality of reinforcing plates 13, 13 ... Are arranged in parallel in the diametrical direction in a cylindrical body 12 to reinforce the body 12, Reinforcement plate 13,13 ...
The two are connected and fixed by connecting rods 14 and 14, and a circular upper plate 15 is welded to the upper end of the opening of the case 12 by circumferential welding 16,
The upper plate 15 is provided with a plurality of support fitting holes 15a for fitting and supporting a lower portion of a support fitting of a fuel assembly (not shown).
上記周溶接16や胴12の継目の縦溶接17等の溶接部およ
びその周辺部には長年の原子炉運転により応力腐食割れ
が発生するおそれがあり、この応力腐食割れが発展する
と亀裂を発生せしめ、炉心支持板10に損傷を与える場合
がある。There is a possibility that stress corrosion cracking may occur in the welded portion such as the circumferential weld 16 and the vertical weld 17 of the joint of the body 12 and its peripheral portion due to long-term reactor operation, and if this stress corrosion cracking develops, cracks may occur. , The core support plate 10 may be damaged.
この場合には炉心支持板10による燃料集合体の支持機
能が害され、原子炉運転に支障を来たすおそれがあると
共に、二次災害を招くおそれもある。In this case, the function of supporting the fuel assembly by the core support plate 10 may be impaired, impairing the operation of the reactor, and possibly causing a secondary disaster.
したがって、炉心支持板10は勿論のこと、原子炉圧力
容器1内の炉心構造物や各種炉内機器の各種点検や検査
が極めて重要な意義を有する。Therefore, not only the core support plate 10, but also various inspections and inspections of the core structure in the reactor pressure vessel 1 and various in-core equipments are extremely important.
しかし、原子炉圧力容器1内は高い放射線線量下にあ
るので、作業員が炉内構造物や各種炉内機器に直接接近
して各種点検や検査を行なうことは不可能である。However, since the inside of the reactor pressure vessel 1 is under a high radiation dose, it is impossible for an operator to directly approach the in-core structure and various in-core equipment to perform various inspections and inspections.
そこで、従来の炉内構造物等の点検等では原子炉圧力
容器1内に立入らずに、その上方から検査機器を吊り下
げて行なっている。Therefore, in the inspection of the conventional reactor internal structure and the like, the inspection equipment is suspended from above the reactor pressure vessel 1 without going into the reactor pressure vessel 1.
例えば炉心支持板10を検査する場合には、検査機器を
先端に取付けた長尺のポールを原子炉圧力容器1内にそ
の上方から挿入して行なうことが一般的である。For example, when inspecting the core support plate 10, it is common to insert a long pole having inspection equipment attached to the tip into the reactor pressure vessel 1 from above.
しかし、このような検査方法では炉心支持板10の上方
に上部格子板9があるので、この上部格子板9が上記長
尺ポールと干渉するおそれがある。However, in such an inspection method, since the upper grid plate 9 is located above the core support plate 10, the upper grid plate 9 may interfere with the long pole.
したがって、良好な点検作業性を確保するためには、
上部格子板9を原子炉圧力容器1より取外す必要があ
る。Therefore, in order to ensure good inspection workability,
It is necessary to remove the upper lattice plate 9 from the reactor pressure vessel 1.
しかしながら、この上部格子板9の取外しは、全ての
燃料集合体および制御棒の取外しを意味し、その着脱作
業に困難を要することはもとより、作業に長時間を要し
てしまう。However, the removal of the upper lattice plate 9 means the removal of all the fuel assemblies and the control rods, and not only the attachment / detachment work is difficult but also the work takes a long time.
さらに、上部格子板9を取外した後、再度原子炉圧力
容器1内に取付ける場合には芯出し等の問題も発生し、
仮に正確な芯出しを行なわない場合には、制御棒の挿入
特性を損うことも予想される。これらの点を考慮する
と、上部格子板9の取外しは極力避けるべきである。Furthermore, when the upper lattice plate 9 is removed and then mounted in the reactor pressure vessel 1 again, problems such as centering may occur.
If accurate centering is not performed, the insertion characteristics of the control rod may be impaired. Considering these points, removal of the upper lattice plate 9 should be avoided as much as possible.
(発明が解決しようとする課題) 上記したように従来の炉芯支持板10の検査方法では検
査作業が非常に困難であり、しかも、上部格子板9を原
子炉圧力容器1より取り外す作業が必要となり、極めて
困難であるという課題がある。(Problems to be Solved by the Invention) As described above, the conventional inspection method of the core support plate 10 is very difficult to perform the inspection work, and moreover, the work of removing the upper lattice plate 9 from the reactor pressure vessel 1 is required. Therefore, there is a problem that it is extremely difficult.
そこで本発明は上記事情を考慮してなされたもので、
その目的は炉心支持板等炉内構造物の検査作業を容易化
し、その作業効率の向上を図ることができる原子炉内検
査装置を提供することにある。Therefore, the present invention has been made in consideration of the above circumstances,
It is an object of the present invention to provide an in-reactor inspecting apparatus that facilitates inspection work of in-core structures such as a core support plate and improves the work efficiency.
(課題を解決するための手段) 本発明は炉心支持板等炉内構造物の検査作業を自動的
に行なうことができるようにした原子炉内検査装置に関
するものである。(Means for Solving the Problems) The present invention relates to an in-reactor inspecting apparatus capable of automatically inspecting an in-core structure such as a core support plate.
すなわち本発明は、原子炉内の炉内構造物を検査する
検査機器を伸縮自在のアーム先端部にそのアーム軸に対
し直角方向の軸周りに回転自在で、かつその軸方向に往
復動自在に保持する保持部と、上記アームを本体ケース
内にその側方に傾動自在に収納する本体と、この本体を
支持部ケースによりその軸周りに旋回自在に支持すると
共に、この支持部ケースの側方に開脚して上記炉内構造
物上に立脚する開閉自在の複数の支持脚を備える支持部
と、この支持部を上記炉内構造物上に起立させる起立位
置の位置決めを行なう位置決め部とを有し、上記保持部
による検査機器の回転および往復動操作と上記アームの
傾動収納および伸縮操作と上記支持部による支持脚の開
閉操作とを遠隔操作自在に構成したことを特徴とする。That is, the present invention provides an inspecting device for inspecting the internal structure of a nuclear reactor in which a telescopic arm tip is rotatable about an axis perpendicular to the arm axis and reciprocally movable in the axial direction. A holding part for holding, a main body for accommodating the arm in a main body case so as to be tiltable laterally, and a main body for supporting the main body so as to be rotatable around its axis by a support part case and at the side of the support part case. A support portion having a plurality of openable and closable support legs that are opened to stand on the in-core structure, and a positioning part that positions the upright position to erect the support part on the in-core structure. It is characterized in that the rotation and reciprocating operation of the inspection device by the holding portion, the tilting accommodation and extension / contraction operation of the arm, and the opening / closing operation of the support leg by the supporting portion can be remotely controlled.
(作用) 原子炉内検査装置が炉内構造物上に降下されると、こ
の炉内構造物上の原子炉内検査装置の設置箇所が位置決
め部により位置決めされ、支持部の各支持脚が遠隔操作
により支持部ケースの側方に開脚して本体を支持する。(Operation) When the in-reactor inspection device is lowered onto the reactor internal structure, the installation position of the reactor internal inspection device on the reactor internal structure is positioned by the positioning unit, and each support leg of the support unit is remote. By operation, the legs are opened to the side of the support case to support the main body.
さらに、遠隔操作によりアームが本体の側方に傾動す
ると共に、本体の軸周りに旋回し、伸縮アームが伸縮
し、検査機器が炉内構造物の検査対象箇所ないし近傍に
移動する。Further, the arm is tilted to the side of the main body by remote control, and is pivoted around the axis of the main body, the telescopic arm is expanded and contracted, and the inspection device is moved to the inspection target portion of the reactor internal structure or its vicinity.
ここで、保持部の適宜遠隔操作により検査機器を回転
あるいは昇降させ、検査機器により所要の検査を行な
う。Here, the inspection device is rotated or moved up and down by an appropriate remote operation of the holding unit, and a required inspection is performed by the inspection device.
したがって本発明によれば、炉内構造物の検査を遠隔
操作により行なうことができるので、その検査の作業効
率の向上と、検査員の放射線被曝線量の低減とを図るこ
とができる。Therefore, according to the present invention, since the inspection of the reactor internal structure can be performed by remote control, the work efficiency of the inspection can be improved and the radiation exposure dose of the inspector can be reduced.
(実施例) 以下本発明の実施例を第1図〜第7図に基づいて説明
する。なお、第1図〜第7図中、第8図〜第10図で示す
部分と共通する部分には同一符号を付している。(Embodiment) An embodiment of the present invention will be described below with reference to FIGS. 1 to 7. In FIGS. 1 to 7, the same parts as those shown in FIGS. 8 to 10 are designated by the same reference numerals.
第1図は本発明の一実施例の全体構成を示す斜視図で
あり、角筒状の本体20はこの本体20と同形同大で軸長が
若干短かい角筒状の支持部30によりその軸周りに旋回自
在に支持され、この本体20と支持部30とは第9図で示す
上部格子板9の格子板同士の間隙である格子目を垂直方
向に挿通する寸法と形とに形成されている。FIG. 1 is a perspective view showing an overall configuration of an embodiment of the present invention. A rectangular tubular main body 20 is provided with a rectangular tubular supporting portion 30 having the same shape and size as the main body 20 and a slightly shorter axial length. The main body 20 and the supporting portion 30 are rotatably supported around the axis thereof, and the main body 20 and the supporting portion 30 are formed in such a size and shape as to vertically insert through the lattice which is a gap between the lattice plates of the upper lattice plate 9 shown in FIG. Has been done.
本体20はその角筒状の本体ケース21の上端と一側面を
開口させた縦溝の収納溝22内に伸縮自在のアーム40を本
体20の側方(水平方向)に傾動自在に収納し、アーム40
の先端部に保持部50を取付けており、保持部50には炉心
支持板10を検査する検査機器60を回転自在かつ昇降自在
に設けている。The main body 20 accommodates a telescopic arm 40 in a sideways (horizontal direction) tiltable body in a storage groove 22 of a vertical groove whose one end is opened and an upper end of a main body case 21 having a rectangular tubular shape, Arm 40
A holding part 50 is attached to the tip of the holding part 50, and an inspection device 60 for inspecting the core support plate 10 is rotatably and vertically movable on the holding part 50.
上記支持部30の下端には位置決め部70の円盤状の大径
端部71が同軸状に固着され、この大径端部71にはこれよ
り小径の挿入用円筒72が一体に連成されている。A disc-shaped large-diameter end portion 71 of the positioning portion 70 is coaxially fixed to the lower end of the support portion 30, and an insertion cylinder 72 having a smaller diameter than this is integrally coupled to the large-diameter end portion 71. There is.
なお、第1図中、符号80は図示しない給電線やエアー
ホース等を内蔵するホースであり、81,82は水中TVカメ
ラ、83は図示しない吊りロープのフック等を引掛ける吊
り耳である。In FIG. 1, reference numeral 80 is a hose containing a power supply line, an air hose and the like (not shown), 81 and 82 are underwater TV cameras, and 83 is a hanging ear for hooking a hook of a hanging rope (not shown).
挿入用円筒72は第2図および第3図に示すように炉心
支持板10における円板状の上板15の中心部にある複数の
支持用嵌合穴15a、もしくは図示しない制御棒案内管の
開口端部内に挿脱自在に挿入され、大径端部71がその支
持用嵌合穴15aもしくは制御棒案内管の開口端周縁部上
に密着されて、本体20の位置決めを行なう。As shown in FIGS. 2 and 3, the inserting cylinder 72 is provided with a plurality of supporting fitting holes 15a in the center of the disk-shaped upper plate 15 of the core supporting plate 10 or a control rod guide tube (not shown). The large-diameter end portion 71 is inserted into the opening end portion so that the large-diameter end portion 71 is brought into close contact with the supporting fitting hole 15a or the opening end peripheral portion of the control rod guide tube to position the main body 20.
また、支持部30は第1図に示すように四角筒状の支持
部ケース31の各面に例えば4脚の支持脚32a,32b,32c,32
dを支持部ケース31の側方に開脚するように開閉自在に
それぞれ配設している。Further, as shown in FIG. 1, the supporting portion 30 has four supporting legs 32a, 32b, 32c, 32 on each surface of a supporting portion case 31 having a rectangular tubular shape.
The d is arranged so as to be openable and closable so as to open to the side of the support case 31.
すなわち、各支持脚32a〜32dは脚ロッド32a1,32b1,32
c1,32d1の先端部に円盤状の脚端32a2,32b2,32c2,32d2の
上面中心部を揺動自在に連結し、これら脚端32a2〜32d2
の下面には第2図および第3図で示す炉心支持板10の支
持用嵌合穴15a内に挿脱自在に嵌入される嵌入円盤32a3,
32b3,32c3,32d3が同軸状に突設され、各支持脚32a〜32d
が炉心支持板12の上板15上に確実に立脚できるようにな
っている。That is, each support leg 32a-32d is a leg rod 32a 1 , 32b 1 , 32.
c 1, a disc-shaped Ashitan 32a 2 to the distal end of 32d 1, 32b 2, 32c 2 , the upper surface center portion of the 32d 2 swingably connected, these Ashitan 32a 2 ~32d 2
The lower surface of the fitting disk 32a 3 , which is removably fitted into the supporting fitting hole 15a of the core support plate 10 shown in FIGS. 2 and 3.
32b 3, 32c 3, 32d 3 is projected coaxially, each support leg 32a~32d
Can reliably stand on the upper plate 15 of the core support plate 12.
各支持脚32a〜32dは第4図に示すように、各脚ロッド
32a1〜32d1が支持ケース31内に挿入されている内端部で
軸ピン33,33…により揺動自在に枢支されると共に、そ
の先端部は閉じスプリング34,34…に連結されて図中上
方に付勢され、各支持脚32a〜32dを図中一点鎖線で示す
ように挿入用円筒72の側面に閉じるようになっている。As shown in FIG. 4, each support leg 32a-32d is attached to each leg rod.
32a 1 to 32d 1 are pivotally supported at their inner ends inserted in the support case 31 by shaft pins 33, 33 ... And their tips are connected to closing springs 34, 34. The support legs 32a to 32d are biased upward in the figure to close the side surfaces of the insertion cylinder 72 as shown by the alternate long and short dash lines in the figure.
また、各脚ロッド32a1〜32d1の各内端はワイヤー35,3
5…を介して挿入用円筒72内に同軸状に形成されたシリ
ンダ73内を往復動するピストン74上に立設されたストッ
パ75に結着され、ピストン74より下方のシリンダ73の下
部室内を図示しない排気チューブにより排気することに
より、各戻しばね34,34…のばね力に抗してピストン74
を図中下方へ降下させ、各支持脚32a〜32dを水平方向に
開脚するようになっている。In addition, the inner ends of the leg rods 32a 1 to 32d 1 are connected to the wires 35, 3
5 is connected to a stopper 75 standing upright on a piston 74 that reciprocates in a cylinder 73 formed coaxially in the insertion cylinder 72, and a lower chamber of the cylinder 73 below the piston 74 is connected to the stopper 75. By exhausting with an exhaust tube (not shown), the piston 74 is resisted against the spring force of each return spring 34, 34.
Is lowered downward in the figure to open the support legs 32a to 32d horizontally.
なお、ストッパ75が図中左右に対向配置された一対の
ローラ76の下面に衝当することによりピストン74の上昇
が規制される。The stopper 75 abuts against the lower surfaces of a pair of rollers 76 that are arranged so as to face each other in the left-right direction in the figure, whereby the rise of the piston 74 is restricted.
支持部ケース31の上端には第4図に示すように旋回用
モータ36が固定され、このモータ36の回転軸36aが本体2
0の本体ケース21の底部中心部に固定されており、支持
部ケース31の上端と本体ケース21の下端との間にベアリ
ング37が介在され、旋回用モータ36の駆動により本体20
がその軸周りに旋回するようになっている。A turning motor 36 is fixed to the upper end of the support case 31 as shown in FIG.
It is fixed to the center of the bottom of the main body case 21 of 0, a bearing 37 is interposed between the upper end of the support case 31 and the lower end of the main body case 21, and the main body 20 is driven by the rotation motor 36.
Is able to turn around its axis.
本体20の収納溝22内に傾動自在に収納されるアーム40
は第5図に示すように、主アーム41の基端部41aの中心
部を本体20の収納溝22の下端部に揺動自在に軸支し、基
端部41aの外面に固着された傾動レバー42の外端に、本
体20の軸方向に上下動する操作シリンダのピストン43の
連接棒43aを枢着している。An arm 40 that is tiltably stored in the storage groove 22 of the main body 20.
5, the central portion of the base end portion 41a of the main arm 41 is swingably supported by the lower end portion of the housing groove 22 of the main body 20, and the tilting fixed to the outer surface of the base end portion 41a. A connecting rod 43a of a piston 43 of an operation cylinder that moves up and down in the axial direction of the main body 20 is pivotally attached to the outer end of the lever 42.
したがって、ピストン43の上下動によりアーム40が本
体20の側方のほぼ水平方向に傾動すると共に、収納溝22
内に収納される。Therefore, the up and down movement of the piston 43 causes the arm 40 to tilt in the lateral direction of the main body 20 in a substantially horizontal direction, and the storage groove 22
It is stored inside.
アーム40は第6図に示すように構成され、角筒状の主
アーム41内で角筒状の伸縮アーム44を出没自在に支持し
ている。The arm 40 is configured as shown in FIG. 6, and supports a telescopic arm 44 having a rectangular tube shape in a main arm 41 having a rectangular tube shape so as to be retractable.
すなわち、アーム40は主アーム41の基端部41a内に内
蔵して固定した駆動用モータ44の回転軸44aに駆動ギヤ4
4bを固着し、この駆動ギヤ44bに、主アーム41内に同軸
状に内蔵したボールねじ45の一端に嵌合した従動ギヤ45
aを噛み合せている。That is, the arm 40 is mounted inside the base end portion 41a of the main arm 41 and fixed to the rotary shaft 44a of the drive motor 44 fixed to the drive gear 4.
4b is fixed, and a driven gear 45 fitted to one end of a ball screw 45 coaxially built in the main arm 41 is fixed to the drive gear 44b.
biting a.
ボールねじ45はそのねじ部の図中左端部外周に螺合す
るボールナット46をフランジ46aを介して主アーム41内
に固定し、一方、ねじ部の図中右端部外周に螺合する移
動用ボールナット47を伸縮アーム44の角筒状基端部に固
定し、この角筒状基端部を角筒状の主アーム41内に挿入
することにより移動用ボールナット47の回転を規制して
いる。The ball screw 45 has a ball nut 46, which is screwed onto the outer periphery of the left end of the screw part in the drawing, is fixed in the main arm 41 via a flange 46a, while being screwed onto the outer periphery of the right end of the screw part in the drawing. The ball nut 47 is fixed to the square tubular base end portion of the telescopic arm 44, and this square tubular base end portion is inserted into the square tubular main arm 41 to regulate the rotation of the moving ball nut 47. There is.
したがって、駆動用モータ44を駆動することによりギ
ヤ44b,45aを介してボールねじ45が回転し、移動用ボー
ルナット47がボールねじ45上を軸方向に移動して伸縮ア
ーム44が軸方向に伸縮する。Therefore, by driving the drive motor 44, the ball screw 45 rotates via the gears 44b and 45a, the moving ball nut 47 moves axially on the ball screw 45, and the telescopic arm 44 expands and contracts in the axial direction. To do.
伸縮アーム44の先端部に固着された保持部50は第7図
に示すように構成され、伸縮アーム44の先端に固着され
た上部ケース51と下部ケース52との間にはベアリング53
が介在されている。The holding portion 50 fixed to the tip end of the telescopic arm 44 is configured as shown in FIG. 7, and a bearing 53 is provided between the upper case 51 and the lower case 52 fixed to the tip end of the telescopic arm 44.
Is intervening.
上部ケース51内に内蔵されて固定されたモータ51aの
回転軸51bは下部ケース52の上端部中心部に固着され、
モータ51aの駆動により、その回転軸51b周りに下部ケー
ス52が回転するようになっている。The rotating shaft 51b of the motor 51a which is built in and fixed in the upper case 51 is fixed to the center of the upper end of the lower case 52,
By driving the motor 51a, the lower case 52 rotates around its rotation shaft 51b.
下部ケース52内には揺動ピストン53を上下動させるシ
リンダ54が形成され、シリンダ54の上部側面に上部孔54
aが、また、その下部側面に下部孔54bがそれぞれ穿設さ
れている。A cylinder 54 for vertically moving the swinging piston 53 is formed in the lower case 52, and an upper hole 54 is formed in an upper side surface of the cylinder 54.
Further, a and a lower hole 54b are formed in the lower side surface thereof.
また、上、下部孔54a,54bには一対のエアーホース55
a,55bが気密に接続され、上部孔54aからシリンダ54の上
部室に圧縮空気を供給することによりピストン53を下方
に押し下げる一方、下部孔54bからシリンダ54の下部室
に圧縮空気を供給することによりピストン53を上方に押
し上げ、ピストン53を上下方向に揺動するようになって
いる。Also, a pair of air hoses 55 are installed in the upper and lower holes 54a and 54b.
a and 55b are airtightly connected to each other, so that the piston 53 is pushed downward by supplying compressed air from the upper hole 54a to the upper chamber of the cylinder 54, while supplying compressed air to the lower chamber of the cylinder 54 from the lower hole 54b. With this, the piston 53 is pushed upward and the piston 53 is swung in the vertical direction.
ピストン53のピストンロッド53aの下端部は下部ケー
ス52の底壁から外部へ延出して検査機器60を内蔵する機
器ケース61に固着され、機器ケース61内には水中ライト
62と水中TVカメラ63等の検査機器が内蔵され、水中TVカ
メラ63の撮影方向を水中ライト62により照明するように
なっている。The lower end of the piston rod 53a of the piston 53 extends outward from the bottom wall of the lower case 52 and is fixed to a device case 61 containing the inspection device 60.
An inspection device such as 62 and the underwater TV camera 63 is built in, and the shooting direction of the underwater TV camera 63 is illuminated by the underwater light 62.
なお、水中TVカメラ63は必要に応じて超音波探傷装置
等他の検査機器に置換し、あるいは併設してもよい。The underwater TV camera 63 may be replaced with another inspection device such as an ultrasonic flaw detector, or may be installed side by side, if necessary.
したがって、検査機器60はモータ51aの回転軸51b周り
に回転すると共に、ピストンロッド53aにより上下動す
ることができる。Therefore, the inspection device 60 can rotate around the rotation shaft 51b of the motor 51a and can move up and down by the piston rod 53a.
次に本実施例の作用を説明する。 Next, the operation of this embodiment will be described.
まず、炉心支持板10において、検査しようとする箇所
の図示しない燃料集合体と制御棒、並びに本実施例の原
子炉内検査装置を設置しようとする箇所の図示しない燃
料支持金具と制御棒案内管を炉心支持板10から取り外
す。First, in the core support plate 10, fuel assemblies and control rods (not shown) at locations to be inspected, and fuel support fittings and control rod guide tubes (not shown) at locations to install the in-reactor inspection apparatus of this embodiment Are removed from the core support plate 10.
次に、本実施例の原子炉内検査装置のアーム40を本体
20の収納溝22内に収納すると共に、支持脚32a〜32dを支
持部ケース31の側面に閉じておく。Next, the arm 40 of the in-reactor inspection apparatus of this embodiment is installed in the main body.
The support legs 32a to 32d are stored in the storage groove 22 of 20 and closed to the side surface of the support case 31.
しかる後に、原子炉内検査装置の吊り耳83に引掛けた
図示しない吊りロープを介して天井クレーン等により懸
吊して原子炉圧力容器1内に吊り込む。Then, it is suspended by an overhead crane or the like via a suspension rope (not shown) hooked on the suspension ear 83 of the in-reactor inspection device and suspended in the reactor pressure vessel 1.
そして、原子炉内検査装置を上部格子板9の間隙であ
る格子目を挿通させてから、遠隔操作により各支持脚32
a〜32dを開脚させ、炉心支持板10上に降すと、挿入用円
筒72が炉心支持板10の支持用嵌合穴15aもしくは制御棒
案内管の開口端内に挿入されて、位置決めが行なわれ、
第2図および第3図に示すように開脚した各支持脚32a
〜32dにより本体20が確実に自立する。Then, after the inspection device inside the nuclear reactor is inserted through the lattices which are the gaps of the upper lattice plate 9, each support leg 32 is remotely operated.
When the legs a to 32d are opened and lowered onto the core support plate 10, the insertion cylinder 72 is inserted into the support fitting hole 15a of the core support plate 10 or the open end of the control rod guide tube for positioning. Done,
Each support leg 32a opened as shown in FIG. 2 and FIG.
~ 32d ensures that the body 20 is self-supporting.
この後、遠隔操作によりアーム40を第1図〜第3図に
示すようにほぼ水平方向に傾動させてから、支持部30の
駆動モータ36を所要方向に回転させてアーム40を本体20
周りに旋回させ、検査対象箇所の方角にアーム40を移動
させる。Thereafter, the arm 40 is tilted in a substantially horizontal direction by remote control as shown in FIGS. 1 to 3, and then the drive motor 36 of the support portion 30 is rotated in a required direction to move the arm 40 to the main body 20.
The arm 40 is swung around and the arm 40 is moved in the direction of the inspection target location.
次いで、遠隔操作によりアーム40を伸縮させて検査機
器60を検査対象箇所ないしその近傍に移動させる。Next, the arm 40 is expanded and contracted by remote control to move the inspection device 60 to the inspection target location or its vicinity.
そして、保持部50のモータ51aとピストン53の駆動を
適宜制御して、水中ライト62により照明し、水中TVカメ
ラ63,81,82により検査対象箇所やその他の箇所を撮影
し、図示しないモニターに映し出す。Then, by appropriately controlling the drive of the motor 51a and the piston 53 of the holding unit 50, the underwater light 62 illuminates, the underwater TV camera 63, 81, 82 to photograph the inspection target part and other parts, and to monitor (not shown). Project.
したがって、モニターを監視することにより炉心支持
板10の検査箇所等を検査することができる。Therefore, it is possible to inspect the inspection location and the like of the core support plate 10 by monitoring the monitor.
検査終了後はまず、アーム40の伸縮アーム44を収縮し
て本体ケース21の収納溝22内に収納し、各支持脚32a〜3
2dを支持部ケース31の側面に閉脚させる。After completion of the inspection, first, the telescopic arm 44 of the arm 40 is contracted to be housed in the housing groove 22 of the main body case 21, and the support legs 32a to 3a.
2d is closed on the side surface of the support case 31.
次に、吊りロープを巻き上げ、原子炉内検査装置を上
部格子板9の格子目を挿通させて引き上げる。Next, the suspension rope is wound up, and the in-reactor inspection device is inserted through the lattice of the upper lattice plate 9 and pulled up.
したがって本実施例によれば、原子炉内検査装置の遠
隔操作により炉心支持板10の検査を行なうことができる
ので、検査員の被曝線量の低減を図ることができる。Therefore, according to the present embodiment, since the core support plate 10 can be inspected by remote operation of the in-reactor inspection device, it is possible to reduce the radiation dose of the inspector.
しかも、原子炉圧力容器1内の上部格子板9を取り外
す必要がないので、炉心支持板10の検査作業が著しく容
易となるうえに、検査時間の大幅な短縮を図ることがで
きる等、検査作業の効率を向上させることができる。Moreover, since it is not necessary to remove the upper lattice plate 9 in the reactor pressure vessel 1, the inspection work of the core support plate 10 is significantly facilitated and the inspection time can be shortened significantly. The efficiency of can be improved.
なお、本実施例では炉心支持板10を検査する場合につ
いて説明したが、本発明はこれに限定されるものではな
く、例えば炉心シュラウド11(第9図参照)や上部格子
板9の検査装置として構成してもよい。In addition, although the case where the core support plate 10 is inspected has been described in the present embodiment, the present invention is not limited to this, and as an inspection device for the core shroud 11 (see FIG. 9) and the upper lattice plate 9, for example. You may comprise.
以上説明したように本発明によれば、原子炉内に収容
された炉内構造物を遠隔操作により検査することができ
るので、その検査の作業効率の向上と、検査員の放射線
被曝線量の低減とを図ることができる。As described above, according to the present invention, since it is possible to inspect the reactor internals housed in the nuclear reactor by remote control, the inspection work efficiency is improved and the radiation exposure dose of the inspector is reduced. Can be achieved.
第1図は本発明の一実施例の全体構成を示す斜視図、第
2図は第1図で示す実施例の原子炉内検査装置が炉心支
持板上に立脚している状態を示す部分平面図、第3図は
第2図の一部を縦断面で示す図、第4図は第1図で示す
支持部の部分断面図、第5図は第1図で示すアームの傾
動状態を示す正面図、第6図は第5図の一部を縦断面で
示す図、第7図は第1図で示す保持部の一部を縦断面で
示す図、第8図はBWR型原子炉の一般的構成を示す縦断
面図、第9図は第8図で示す炉心支持構造物の縦断面
図、第10図は第8図で示す炉心支持板の一部を切欠いて
示す一部切欠斜視図である。 20……本体、21……本体ケース、30……支持部、31……
支持部ケース、32a〜32d……支持脚、40……アーム、41
……主アーム、44……伸縮アーム、50……保持部、60…
…検査機器、70……位置決め部。FIG. 1 is a perspective view showing the overall configuration of an embodiment of the present invention, and FIG. 2 is a partial plan view showing a state in which the in-reactor inspecting apparatus of the embodiment shown in FIG. 1 is standing on a core support plate. FIGS. 3 and 3 show a part of FIG. 2 in a longitudinal cross section, FIG. 4 shows a partial cross section of the support shown in FIG. 1, and FIG. 5 shows the tilted state of the arm shown in FIG. A front view, FIG. 6 is a vertical cross-sectional view of a part of FIG. 5, FIG. 7 is a vertical cross-sectional view of a part of the holding part shown in FIG. 1, and FIG. 8 is a BWR reactor. FIG. 9 is a vertical cross-sectional view showing a general structure, FIG. 9 is a vertical cross-sectional view of the core support structure shown in FIG. 8, and FIG. 10 is a partially cutaway perspective view showing a part of the core support plate shown in FIG. It is a figure. 20 …… Main body, 21 …… Main body case, 30 …… Supporting part, 31 ……
Support case, 32a to 32d …… Support legs, 40 …… Arm, 41
...... Main arm, 44 …… Extensible arm, 50 …… Holding part, 60…
… Inspection equipment, 70 …… Positioning unit.
Claims (1)
を伸縮自在のアーム先端部にそのアーム軸に対し直角方
向の軸周りに回転自在で、かつその軸方向に往復動自在
に保持する保持部と、上記アームを本体ケース内にその
側方に傾動自在に収納する本体と、この本体を支持部ケ
ースによりその軸周りに旋回自在に支持すると共に、こ
の支持部ケースの側方に開脚して上記炉内構造物上に立
脚する開閉自在の複数の支持脚を備える支持部と、この
支持部を上記炉内構造物上に起立させる起立位置の位置
決めを行なう位置決め部とを有し、上記保持部による検
査機器の回転および往復動操作と上記アームの傾動収納
および伸縮操作と上記支持部による支持脚の開閉操作と
を遠隔操作自在に構成したことを特徴とする原子炉内検
査装置。Claim: What is claimed is: 1. An inspection device for inspecting reactor internals in a nuclear reactor, wherein an extendable arm tip is rotatable about an axis perpendicular to the arm axis and reciprocally movable in the axis direction. A holding part for holding, a main body for accommodating the arm in a main body case so as to be tiltable laterally, and a main body for supporting the main body so as to be rotatable around its axis by a support part case and at the side of the support part case. A support portion having a plurality of openable and closable support legs that are opened to stand on the in-core structure, and a positioning part that positions the upright position to erect the support part on the in-core structure. An inside of a nuclear reactor characterized in that the operation of rotating and reciprocating the inspection equipment by the holding part, the tilting storage and expansion / contraction of the arm, and the opening / closing operation of the supporting leg by the supporting part can be remotely controlled. Inspection device.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP63079711A JP2529994B2 (en) | 1988-03-31 | 1988-03-31 | In-reactor inspection device |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP63079711A JP2529994B2 (en) | 1988-03-31 | 1988-03-31 | In-reactor inspection device |
Publications (2)
Publication Number | Publication Date |
---|---|
JPH01250895A JPH01250895A (en) | 1989-10-05 |
JP2529994B2 true JP2529994B2 (en) | 1996-09-04 |
Family
ID=13697792
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP63079711A Expired - Fee Related JP2529994B2 (en) | 1988-03-31 | 1988-03-31 | In-reactor inspection device |
Country Status (1)
Country | Link |
---|---|
JP (1) | JP2529994B2 (en) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP3868669B2 (en) * | 1999-06-11 | 2007-01-17 | 株式会社東芝 | Core shroud inner diameter automatic measuring device |
JP4634865B2 (en) * | 2005-06-02 | 2011-02-16 | 株式会社東芝 | Furnace bottom inspection repair device and method |
-
1988
- 1988-03-31 JP JP63079711A patent/JP2529994B2/en not_active Expired - Fee Related
Also Published As
Publication number | Publication date |
---|---|
JPH01250895A (en) | 1989-10-05 |
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